CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
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P. K. Sharma
Abstract
The thermal pollution arising out of discharge of hot water from the power plant condensers into the natural water bodies such as rivers, lakes, reservoirs, oceans etc. has been a serious concern to environmentalists ever since the plants started operating world over. In the past forty to fifty years, the methods of calculations for predicting the velocity and temperature fields in the affected regions of the stagnant/flowing water bodies have undergone a significant improvement. Currently, use of Computational Fluid Dynamics (CFD) codes for performing these calculations is gaining popularity. However, several factors such as the assumed computational domain and its discretisation, the boundary conditions used, representation of hydrodynamic characteristics (laminar/turbulent, buoyant/non-buoyant), etc. have a strong influence on the accuracy of predictions by such a model. A CFD code STAR-CD has been used for analyzing the thermal plume behaviour in the Kadra reservoir at Kaiga Atomic Power Station (KAPS). The predictions from these calculations of two units in operation have been found to be in good agreement with the site data made available from earlier studies. The present paper briefly describes the model developed using STAR-CD and results obtained for the Kadra reservoir at KAPS.
Kurzfassung
Die Wärmebelastung durch die Ableitung von heißem Wasser aus den Kraftwerkskondensatoren in natürliche Gewässer, wie z.B. Flüsse, Seen, Reservoirs, Meere etc. ist ein ernstes Anliegen von Umweltschützern weltweit seit es Kraftwerke gibt. In den vergangenen 40–50 Jahren haben sich die Berechnungsmethoden zur Vorhersage der Geschwindigkeits- und Temperaturfelder in den betroffenen Regionen stark verbessert. Zur Zeit gewinnt die Verwendung von Computational Fluid Dynamics (CFD) Codes für diese Art Berechnungen immer mehr an Bedeutung. Verschiedene Faktoren, wie z.B. das angenommene Berechnungsgebiet und seine Diskretisierung, die verwendeten Randbedingungen, die Darstellung der hydrodynamischen Eigenschaften (laminar/turbulent, buoyant/nicht-buoyant), etc. haben einen starken Einfluss auf die Genauigkeit der Vorhersagen eines solchen Modells. Der CFD Code STAR-CD wurde verwendet zur Analyse des Verhaltens der Wärmeableitungen im Kadra Reservoir beim Kaiga Kernkraftwerk (KAPS). Die mit Hilfe dieser Berechnungen erhaltenen Vorhersagen für die beiden in Betrieb befindlichen Kraftwerkseinheiten stimmen gut überein mit den Daten vor Ort aus früheren Studien. Die vorliegende Arbeit beschreibt das mit Hilfe von STAR-CD entwickelte Modell und die für das Reservoir beim Kaiga Kernkraftwerk (KAPS) erhaltenen Ergebnisse.
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© 2011, Carl Hanser Verlag, München
Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
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- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
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- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Comparison between CAREB code calculations and LOCA test results in the FUMEX III project
- Calculation of moderator circulation in IPHWR using a porosity approach
- Simulation of natural circulation in a rectangular loop using CFD code PHOENICS
- CFD analysis of passive autocatalytic recombiner interaction with atmosphere
- Review and investigations of oscillatory flow behaviour of a horizontal ceiling opening for nuclear containment and fire safety analysis
- CFD simulation of thermal discharge behaviour in the Kadra reservoir at the Kaiga atomic power station
- Inverse problems using Artificial Neural Networks in long range atmospheric dispersion
- Sipping tests for the irradiated fuel elements of the TR-2 research reactor
- Neutron multiplication in source driven subcritical nuclear systems
- Cyclotron production of 101Pd/101mRh radionuclide generator for radioimmunotherapy
- Investigation of cross sections of reactions used in neutron activation analysis
- Modified UN method for the reflected critical slab problem with forward and backward scattering
